Effect of thermal aging on mechanical properties of cast stainless steels
A procedure and correlations are presented for predicting mechanical properties of cast stainless steels in service at temperatures <450{degrees}C from known material information. The ``saturation`` fracture properties of a cast stainless steel, i.e., the minimum values that would be achieved for the material after long-term service, are estimated from the chemical composition of the steel. Fracture properties as a function of time and temperature of service are estimated from the kinetics of embrittlement, which are also determined from chemical composition. The correlations successfully predict fracture toughness, Charpy-impact, and tensile properties of cast stainless steels from the Shippingport-, Ringhals-, and Gundremmingen-reactor components.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 195753
- Report Number(s):
- ANL/ET/CP-86085; CONF-950908-10; ON: DE96005237; TRN: 96:008308
- Resource Relation:
- Conference: 2. international conference on heat resistant materials, Gatlinburg, TN (United States), 11-14 Sep 1995; Other Information: PBD: Mar 1995
- Country of Publication:
- United States
- Language:
- English
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Mechanical properties of thermally aged cast stainless steels from Shippingport reactor components
Mechanical properties of thermally aged cast stainless steels from shippingport reactor components.
Related Subjects
22 NUCLEAR REACTOR TECHNOLOGY
STAINLESS STEELS
MECHANICAL PROPERTIES
THERMAL DEGRADATION
REACTOR COMPONENTS
EMBRITTLEMENT
FRACTURE PROPERTIES
TENSILE PROPERTIES
IMPACT STRENGTH
CHARPY TEST
TEMPERATURE DEPENDENCE
TIME DEPENDENCE
SHIPPINGPORT REACTOR
RINGHALS-1 REACTOR
RINGHALS-2 REACTOR
RINGHALS-3 REACTOR
RINGHALS-4 REACTOR
GUNDREMMINGEN-2 REACTOR
GUNDREMMINGEN-3 REACTOR
AGING